EP2599088B1 - Verfahren zur steuerung der positionen von kernbrennstabbündeln in einem kernreaktorkern und zugehörige steueranordnung - Google Patents

Verfahren zur steuerung der positionen von kernbrennstabbündeln in einem kernreaktorkern und zugehörige steueranordnung Download PDF

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Publication number
EP2599088B1
EP2599088B1 EP11752292.0A EP11752292A EP2599088B1 EP 2599088 B1 EP2599088 B1 EP 2599088B1 EP 11752292 A EP11752292 A EP 11752292A EP 2599088 B1 EP2599088 B1 EP 2599088B1
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Prior art keywords
positions
nuclear fuel
fuel assemblies
holes
core plate
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EP11752292.0A
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English (en)
French (fr)
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EP2599088A1 (de
Inventor
Audrey Tournant
Frédéric Alain MAGRE
Benjamin Loriot
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Areva NP SAS
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Areva NP SAS
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/08—Structural combination of reactor core or moderator structure with viewing means, e.g. with television camera, periscope, window
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/19—Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention generally relates to methods for controlling the positions of nuclear fuel assemblies within the core of a nuclear reactor.
  • the core of a nuclear reactor typically comprises a plurality of nuclear fuel assemblies of prismatic shape, resting on a core support plate. Above the assemblies is placed a top plate of heart (PSC) intended, inter alia, to lock in position the upper ends of the nuclear fuel assemblies.
  • PSC top plate of heart
  • the upper ends of the nuclear fuel assemblies typically each comprise two holes, called “S-holes", intended to cooperate with centering pins of the upper core plate.
  • the centering pins project under the upper plate of heart and are each engaged in a hole S.
  • the nuclear fuel assemblies are first put in place inside the reactor core, then the upper core plate and other reactor internals are replaced.
  • the pins enter the S-holes. If the pins and S-holes of some assemblies are offset relative to each other, the PSC pieces may have entered forcefully. in some S holes.
  • the invention aims to provide a method for controlling the positions of a plurality of nuclear fuel assemblies relative to the upper core plate, which is fast and reliable.
  • the method of the invention aims to control the positions of a plurality of nuclear fuel assemblies 1 with respect to an upper core plate 3 in the core 5 of a nuclear reactor.
  • the core 5 of a nuclear reactor is partially shown, schematically, on the figures 1 and 2 .
  • the core 5 comprises a large number of nuclear fuel assemblies 1, of prismatic shapes.
  • Each assembly 1 has an elongated shape along the central axis X of the nuclear reactor core.
  • the assemblies 1 are arranged in the heart of the nuclear reactor next to each other, so that the side faces 6 of two adjacent assemblies are facing each other and in the immediate vicinity of one of the other.
  • Each assembly comprises a frame inside which are placed nuclear fuel rods.
  • the frame includes, inter alia, an upper end and a lower end.
  • the assemblies 1 rest by their lower ends on a bottom plate of heart, not shown.
  • the upper core plate 3 is arranged axially immediately above the assemblies 1.
  • the core further comprises a substantially cylindrical core envelope 7, coaxial with the axis X.
  • the envelope 7 contributes to channeling the circulation of the primary fluid in the reactor core.
  • a partition 9 is placed around the fuel assemblies 1, between the assemblies 1 and the core shell 7. The function of the partition 9 is to block the assemblies 1 in position, and contributes to channeling the circulation of the primary fluid through the assemblies.
  • the assemblies are positioned in the core in a regular manner, for example according to a square-pitch grating.
  • the top plate of heart 3 is a substantially circular plate of external diameter substantially corresponding to the internal diameter of the core envelope 7. It is centered on the axis X and substantially perpendicular to the axis X. It has a plurality of orifices 11, for example intended for the passage of the guide tubes of the reactivity control clusters of the reactor, or for the circulation of the primary fluid. Only a portion of the orifices 11 is shown on the figure 3 .
  • the core support plate 3 is locked in position angularly about the central axis X with respect to the core shell 5 by pins 13 rigidly fixed to the core shell.
  • the pins 13 protrude radially inwardly of the core shell 7 relative to the radially inner surface 15 of the core shell ( figures 2 , 4, 5 ).
  • notches 17 formed at the periphery of the upper core plate 3.
  • the notches 17 each have a circumferential width slightly greater than that of the guide pins 13.
  • the notches 17 extend axially over the entire thickness of the upper core plate.
  • the pins 13 are engaged in the notches 17, the upper core plate 3 thus being locked in rotation relative to the core shell 5 and free axially relative thereto.
  • the upper core plate 3 has on a lower face 19 facing the nuclear fuel assemblies 1 a plurality of centering pins 21 ( figure 6 ).
  • the pins 21 protrude from the face 19 to the fuel assemblies.
  • the upper ends 23 of the fuel assemblies typically each have two holes 25 each intended to receive a pin 21, called S-holes.
  • figure 8 seen in section perpendicular to the X axis, the upper end pieces 23 have a square section, the holes S 25 being located at two opposite angles of said section.
  • the holes S 25 are open upwards, that is to say towards the upper plate of heart, as visible on the figure 6 .
  • the pins 21 have the function of maintaining in position each the upper end of an assembly 1.
  • the control method of the invention is intended to verify that the nuclear fuel assemblies, after loading in the core, are well positioned with respect to the upper core plate 3. More specifically, the method aims to determine whether the holes S 25 of the nuclear fuel assemblies are positioned correctly with respect to the pins 21 of the upper core plate.
  • the reference point is preferably an element whose position is known with good accuracy with respect to the upper core plate.
  • the reference point is one of the guide pins 13 for indexing in position the upper core plate relative to the core shell.
  • the uncertainty on the positions of the pins 21 with respect to the centering pins 13 is of the order of 1 millimeter.
  • the determination of the positions of the holes S 25 of the nuclear fuel assemblies with respect to the reference point is carried out by taking images of the assemblies 1, and by determining with the aid of said images the positions of the holes S with respect to the point reference.
  • each fuel assembly 1 an image is acquired for each fuel assembly 1.
  • the image pickup device is placed above the upper nozzle 23 of the assembly to be photographed, the optical axis of the pickup apparatus image being substantially parallel to the central axis X.
  • the size of each acquired image is adapted to allow identification on said image of the holes S of the photographed assembly, and of at least one hole S25 of an assembly of nuclear fuels adjacent to the photographed assembly.
  • each assembly 29 is surrounded by eight adjacent assemblies 31.
  • the upper end of each assembly has two holes S 25 arranged at two angles of the tip located on a diagonal. Typically, all the assemblies are arranged in the same orientation, so that the holes S 25 of the different assemblies are located on the same diagonal.
  • several of the assemblies 31 adjacent to the assembly 29 have on the edges next to the assembly 29 a hole S 25.
  • six of the neighboring assemblies of the assembly 29 have a hole S 25 adjacent to the assembly 29.
  • the image of the assembly 29 allows the identification not only of the two holes S of the assembly 29, but also of a hole S for six of the neighboring assemblies.
  • images are acquired by assembly in a predefined order. For example, assemblies are treated row by row. A first row is thus traversed from the assembly located at a first end of the row. The neighboring assembly is then photographed, and the row is followed to the assembly at the second end of the row. The neighboring row is then processed, for example in the opposite direction. Such an S-course minimizes the travel time of the image pickup apparatus from one assembly to another.
  • an overall picture of all the nuclear fuel assemblies is made from the previously acquired images.
  • the overall image gives the positions of all the holes S of all the nuclear fuel assemblies with respect to each other.
  • the overall image is made by merging the images acquired by calculation.
  • the positions of the different images relative to each other can be fine-tuned because each image has S-holes 25 also on other images, as indicated above.
  • the positions of the holes S with respect to the reference point are then determined from the overall image. To do this, it is necessary to know precisely the position of at least one hole 25 relative to the reference point.
  • This position can be determined in many ways. For example, it is possible to acquire an additional image, showing both the guide pin serving as a reference point and the holes 25 of an assembly located near the pin 13.
  • the comparison of the positions of the holes S and the positions of the pins is performed by comparing the overall image previously made to a theoretical image of the upper core plate giving the positions of the different centering pins relative to the reference point.
  • This image typically is a predetermined digital image, stored in a database. For example, it is reconstituted from the production planes of the elements of the core of the nuclear reactor, in particular the plans for manufacturing the core envelope and the upper core plate.
  • the comparison is made by superimposing the overall image on the theoretical image of the upper core plate.
  • the superposition is performed on a calculator, automatically. Alternatively, the superposition is performed manually by an operator.
  • the gap between the hole S and the corresponding pin 21 of the upper core plate 3 is determined.
  • Said positions correspond to the positions in a plane substantially perpendicular to the central axis X of the reactor core.
  • the spacing corresponds to the distance between the two centers in said plane perpendicular to the axis X. The spacing is calculated automatically, or determined graphically by an operator.
  • the limit is for example equal to 8 millimeters, preferably equal to 4 millimeters, and more preferably equal to 2 millimeters.
  • the assembly is considered to be poorly positioned relative to the upper core plate. If, on the contrary, the deviations found for all the holes S of an assembly are below the limit, the assembly is considered to be well positioned relative to the upper plate of the core.
  • the method provides a list of all S25 holes that are out of tolerance, i.e., the calculated deviations of which are greater than the predetermined limit.
  • the method also makes it possible to provide a list of incorrectly positioned assemblies, possibly with the identification numbers of the incorrectly positioned assemblies.
  • the method can also provide the inter-assemblies, calculated from the positions of the S25 holes of the different assemblies.
  • the method described above can be implemented by the device shown schematically on the figure 1 .
  • the device 33 comprises an imaging device 35, and a computer 37.
  • the imaging device 35 comprises a support 39, lighting members 41 fixed on the support 39, a watertight box 43 fixed on the support 39, and a digital imaging apparatus 45 disposed inside the waterproof case.
  • the image pickup device 35 is adapted to be moved by the machine 47 for loading the nuclear fuel assemblies into the reactor core.
  • the support 39 comprises a coupling member designed to cooperate with the mat 49 of the loading machine 47.
  • the device 33 is provided so that the luminous power of the illumination 41 can be adjusted from the computer 37, for example as a function of the surface state of the nuclear fuel assemblies.
  • the camera could also be a digital camera.
  • the camera 45 is connected to the computer 37 by a digital link, allowing the exchange of data between the computer and the camera. This connection is for example of the Ethernet type.
  • the device is adapted to allow the remote control of the camera via the computer 37, and the repatriation of the images from the camera 45 to the computer 37.
  • the box 43 is connected to a ventilation system, not shown, and maintained at an internal pressure of 2 bar.
  • control method includes a step of determining the positions of the S-holes of the nuclear fuel assemblies with respect to a reference point in the internal equipment or in the reactor vessel, and a step of acquisition positions of the centering pins of the upper core plate vis-à-vis the same reference point, it is possible to make a very accurate comparison of the positions of the holes S and the positions of the corresponding pins.
  • the use as a reference point of the guide pin of the upper core plate is particularly well suited because the position of the upper core plate is known precisely with respect to this pin.
  • the positions of the holes S with respect to the reference point can be conveniently and quickly determined by taking images of the assemblies using suitable equipment.
  • the use of a global image of the nuclear fuel assemblies, constituted by merging the different images taken with the aid of the imaging device, makes it possible to make a quick and accurate comparison with the position of the pins of the upper plate. of heart. This speeds up the process.
  • the overall image can be constructed with good accuracy if each image taken with the imaging device gives not only the positions of the holes S of a given assembly, but also at least one hole S of another assembly, serving as a reference point for the juxtaposition of the different images.
  • the process is particularly rapid, the implementation time being for example about four hours for the entire core of a nuclear reactor. This is particularly important because the positional control of the nuclear fuel assemblies with respect to the upper core plate is on the critical path during unloading and reloading operations of the nuclear fuel assemblies in the reactor core. Since the positions of the S-holes relative to the pions are accurately determined, the risk that the nuclear fuel assemblies get stuck during the lifting of the upper core plate is minimized.
  • the process is applied to at least a quarter of nuclear fuel assemblies of the core, preferably to at least half of the nuclear fuel assemblies of the core, and more preferably all the nuclear fuel assemblies of the core.
  • each image can be adapted to allow viewing of two adjacent assemblies, and thus allow to determine the positions of the holes S of the two assemblies.
  • the size of the images could also be adapted to allow the viewing of four or more assemblies, provided that the resolution of the camera is sufficient.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Claims (10)

  1. Verfahren zur Kontrolle von Positionen einer Mehrzahl von Nuklearbrennstoffanordnungen (1) bezüglich einer oberen Kernplatte (3) in einem Nuklearreaktorkern (5), wobei das Verfahren die folgenden Schritte aufweist:
    - Wählen eines Referenzpunkts (13) in internen Apparaturen oder in einem Reaktorbehälter,
    - Ermitteln von Positionen von Löchern S (25) der Nuklearbrennstoffanordnungen (1) gegenüber dem Referenzpunkt (13), wobei jedes Loch S (25) vorgesehen ist zum Kooperieren mit einem Zentrierstift (21), der zu der oberen Kernplatte (3) gehört,
    - Erlangen von Positionen des Zentrierstifts (21) der oberen Kernplatte (3) gegenüber dem Referenzpunkt (13),
    - Vergleichen der Positionen der Löcher S (25) und der Positionen der Stifte (21), und davon ableiten, ob die Nuklearbrennstoffanordnungen (1) bezüglich der oberen Kernplatte (3) korrekt positioniert sind.
  2. Verfahren gemäß Anspruch 1, dadurch gekennzeichnet, dass der Referenzpunkt ein Führungszapfen (13) ist, der mit einer Umhüllung des Kerns (5) fest verbunden ist, wobei der Führungszapfen (13) vorgesehen ist zum Kooperieren mit einer Aussparung (17) der oberen Kernplatte (3) zum Positionieren der oberen Kernplatte (3) bezüglich der Umhüllung des Kerns (5).
  3. Verfahren gemäß Anspruch 1 oder 2, dadurch gekennzeichnet, dass die Positionen der Löcher S (25) bezüglich des Referenzpunkts (13) ermittelt werden durch Nehmen von Bildern der Nuklearbrennstoffanordnungen (1) und durch Ermitteln, mit Hilfe dieser Bilder, der Positionen der Löcher S (25) bezüglich des Referenzpunkts (13).
  4. Verfahren gemäß Anspruch 3, dadurch gekennzeichnet, dass jedes Bild angepasst ist zum Geben der Positionen der Löcher S (25) wenigstens einer gegebenen Nuklearbrennstoffanordnung (29) und wenigstens eines Lochs S (25) einer Nuklearbrennstoffanordnung (31), die zu der gegebenen Nuklearbrennstoffanordnung (29) benachbart ist.
  5. Verfahren gemäß Anspruch 3 oder 4, dadurch gekennzeichnet, dass ein globales Bild der Mehrzahl von Nuklearbrennstoffanordnungen (1) realisiert ist ausgehend von den Bildern der Nuklearbrennstoffanordnungen (1), wobei das globale Bild die Positionen von allen Löchern S (25) der Mehrzahl von Nuklearbrennstoffanordnungen (1) gibt.
  6. Verfahren gemäß Anspruch 5, dadurch gekennzeichnet, dass der Vergleich der Positionen der Löcher S (25) und der Positionen der Stifte (21) durchgeführt wird durch Vergleichen des globalen Bilds der Mehrzahl von Nuklearbrennstoffanordnungen (1) mit einem theoretischen Bild der oberen Kernplatte (3), welches die Positionen von allen Zentrierstiften (21) gibt, die zu allen Löchern S (25) der Mehrzahl von Nuklearbrennstoffanordnungen (1) korrespondieren.
  7. Verfahren gemäß Anspruch 6, dadurch gekennzeichnet, dass jede Nuklearbrennstoffanordnung (1) betrachtet wird als korrekt positioniert bezüglich der oberen Kernplatte (3), wenn der Vergleich der Position jedes Lochs S (25) dieser Nuklearbrennstoffanordnung (1) mit der Position des korrespondierenden Stifts (21) anzeigt, dass das Loch S (25) und der Stift (21) zwischen sich einen Abstand haben, der kleiner ist als ein vorbestimmtes Limit, z.B. 8 Millimeter.
  8. Verfahren gemäß irgendeinem der Ansprüche 3 bis 7, dadurch gekennzeichnet, dass die Bilder mit Hilfe eines Digital-Bildaufnahmeapparats (45) genommen werden, der von einer Maschine (47) zum Laden der Nuklearbrennstoffanordnungen (1) verlagert wird.
  9. Verfahren gemäß irgendeinem der vorhergehenden Ansprüche, dadurch gekennzeichnet, dass die Mehrzahl von Nuklearbrennstoffanordnungen (1) aufweist wenigstens ein Viertel der Nuklearbrennstoffanordnungen (1) des Kerns (5), bevorzugt wenigstens die Hälfte.
  10. Einrichtung zur Kontrolle von Positionen einer Mehrzahl von Nuklearbrennstoffanordnungen (1) bezüglich einer oberen Kernplatte (3) in einem Nuklearreaktorkern (5), wobei die Einrichtung aufweist:
    - eine Vorrichtung, die angepasst ist zum Ermitteln von Positionen von Löchern S (25) der Nuklearbrennstoffanordnungen (1) gegenüber einem Referenzpunkt (13), wobei jedes Loch S (25) vorgesehen ist zum Kooperieren mit einem Zentrierstift (21), der zu der oberen Kernplatte (3) gehört, wobei der Referenzpunkt (13) gewählt ist in internen Apparaturen oder in einem Reaktorbehälter,
    dadurch gekennzeichnet, dass die Einrichtung zur Kontrolle ferner aufweist:
    - eine Vorrichtung, die angepasst ist zum Ermitteln der Positionen der Zentrierstifte (21) der oberen Kernplatte (3) gegenüber dem Referenzpunkt (13) und
    - eine Vorrichtung, die angepasst ist zum Vergleichen der Positionen der Löcher S (25) und der Positionen des Zapfens (21) und zum davon Ableiten, ob die Nuklearbrennstoffanordnungen (1) korrekt positioniert sind bezüglich der oberen Kernplatte (3).
EP11752292.0A 2010-07-27 2011-07-26 Verfahren zur steuerung der positionen von kernbrennstabbündeln in einem kernreaktorkern und zugehörige steueranordnung Active EP2599088B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR1056132A FR2963473B1 (fr) 2010-07-27 2010-07-27 Procede de controle des positions des assemblages de combustibles nucleaires a l'interieur d'un coeur de reacteur nucleaire, et ensemble de controle correspondant
PCT/FR2011/051793 WO2012022890A1 (fr) 2010-07-27 2011-07-26 Procédé de contrôle des positions des assemblages de combustibles nucléaires à l'intérieur d'un coeur de réacteur nucléaire, et ensemble de contrôle correspondant

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EP2599088A1 EP2599088A1 (de) 2013-06-05
EP2599088B1 true EP2599088B1 (de) 2014-12-03

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US (1) US10083768B2 (de)
EP (1) EP2599088B1 (de)
CN (1) CN103119659B (de)
ES (1) ES2531678T3 (de)
FR (1) FR2963473B1 (de)
WO (1) WO2012022890A1 (de)
ZA (1) ZA201300707B (de)

Cited By (1)

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RU2594173C2 (ru) * 2015-08-27 2016-08-10 Сергей Константинович Манкевич Устройство для контроля точности установки сборок тепловыделяющих элементов в ядерном реакторе

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CN103594132B (zh) * 2012-08-15 2017-02-15 广东核电合营有限公司 核电站堆芯燃料组件实际位置偏差测量方法和系统
CN103811086B (zh) * 2012-11-09 2016-05-04 中国广核集团有限公司 核电站堆芯燃料组件的换料监视方法和系统
FR2999011A1 (fr) * 2012-11-30 2014-06-06 Electricite De France Determination amelioree des positions d'elements d'assemblages combustible
FR3040524B1 (fr) * 2015-08-31 2017-09-08 Electricite De France Procede de cartographie d'assemblages combustibles

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FR2614128B1 (fr) * 1987-04-15 1992-06-12 Electricite De France Outil d'aide au chargement des assemblages combustibles d'un reacteur nucleaire a eau pressurisee 1300 mw
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JP5345951B2 (ja) * 2007-01-02 2013-11-20 ウエスチングハウス・エレクトリック・カンパニー・エルエルシー 原子炉用アラインメント・プレートの構成

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2594173C2 (ru) * 2015-08-27 2016-08-10 Сергей Константинович Манкевич Устройство для контроля точности установки сборок тепловыделяющих элементов в ядерном реакторе

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WO2012022890A1 (fr) 2012-02-23
FR2963473A1 (fr) 2012-02-03
EP2599088A1 (de) 2013-06-05
FR2963473B1 (fr) 2012-09-07
CN103119659A (zh) 2013-05-22
US20130195237A1 (en) 2013-08-01
US10083768B2 (en) 2018-09-25
CN103119659B (zh) 2016-06-01
ES2531678T3 (es) 2015-03-18
ZA201300707B (en) 2014-06-25

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